CN113689964B - Main heat-waste heat integrated heat exchanger of small nuclear reactor - Google Patents
Main heat-waste heat integrated heat exchanger of small nuclear reactor Download PDFInfo
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- CN113689964B CN113689964B CN202111007621.9A CN202111007621A CN113689964B CN 113689964 B CN113689964 B CN 113689964B CN 202111007621 A CN202111007621 A CN 202111007621A CN 113689964 B CN113689964 B CN 113689964B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
- F28D7/00—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall
- F28D7/0066—Multi-circuit heat-exchangers, e.g. integrating different heat exchange sections in the same unit or heat-exchangers for more than two fluids
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
- F28D7/00—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall
- F28D7/16—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged in parallel spaced relation
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/243—Promoting flow of the coolant for liquids
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- General Engineering & Computer Science (AREA)
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- High Energy & Nuclear Physics (AREA)
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- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
Description
技术领域technical field
本发明属于先进核能开发技术领域,具体涉及一种小型核反应堆主热-余热一体式换热器。The invention belongs to the technical field of advanced nuclear energy development, and in particular relates to a main heat-waste heat integrated heat exchanger of a small nuclear reactor.
背景技术Background technique
为匹配小型核反应堆具有体积小、重量轻、成本低等优势,亟待开发相应的小型核反应堆主热和余热换热器,确保反应堆在正常停堆和事故工况下有效导出衰变热,同时具有足够小的体积适应反应堆内部狭窄的空间。然而通常这两类换热器相互独立工作,对减小体积提出了较大挑战。综上,需要对小型核反应堆的主热和余热换热器进行紧凑一体化设计,既不能占用太大体积,也应保证换热强度,并尽量减少热应力。因此,研发适用于小型核反应堆的主热-余热一体式换热器,是反应堆工程的必要环节,有助于推动我国自主掌握小型核反应堆设计技术的进程。In order to match the advantages of small nuclear reactors such as small size, light weight, and low cost, it is urgent to develop corresponding heat exchangers for the main heat and waste heat of small nuclear reactors to ensure that the reactor can effectively dissipate the decay heat under normal shutdown and accident conditions, and at the same time have a sufficiently small The volume fits into the narrow space inside the reactor. However, usually these two types of heat exchangers work independently of each other, which poses a great challenge to reduce the volume. To sum up, it is necessary to carry out a compact and integrated design for the main heat and waste heat exchangers of small nuclear reactors, which should neither occupy too much volume, but also ensure the heat exchange intensity and minimize thermal stress. Therefore, the research and development of the main heat-waste heat integrated heat exchanger suitable for small nuclear reactors is a necessary part of reactor engineering, which will help promote the process of my country's independent mastery of small nuclear reactor design technology.
发明内容Contents of the invention
为了克服上述现有技术存在的问题,本发明公开了一种小型核反应堆主热-余热一体式换热器,为反应堆和余排系统的设计提供设备基础。In order to overcome the above-mentioned problems in the prior art, the present invention discloses a small nuclear reactor main heat-waste heat integrated heat exchanger, which provides an equipment basis for the design of the reactor and the waste exhaust system.
为达到上述目的,本发明采用如下技术方案:To achieve the above object, the present invention adopts the following technical solutions:
一种小型核反应堆主热-余热一体式换热器,包括换热器外壳9,固定连接在换热器外壳9底部和顶部的下封头12和上封头14,位于换热器外壳9内底部中心和下封头12中心处的余热排出系统换热器入口套筒13,位于上封头14中心的余热排出系统换热器出口套筒15,位于换热器外壳9内的管束8,两边的管由上管板10和下管板11固定,中间的管由上管板10和余热排出系统换热器入口套筒13固定;A small nuclear reactor main heat-waste heat integrated heat exchanger, including a
换热器内有三个流体区:壳侧一回路冷却剂区A、管侧主热传输二回路冷却剂区B和管侧余热排出回路冷却剂区C;壳侧一回路冷却剂区A是由位于换热器外壳9内侧与余热排出系统换热器入口套筒13外侧、管束8外侧区域构成的一回路冷却剂流动空间;管侧主热传输二回路冷却剂区B是由位于换热器外壳9与余热排出系统换热器入口套筒13之间的管束8内侧、位于下封头12的环形二回路冷却剂入口腔室和位于上封头14的环形二回路冷却剂出口腔室构成的二回路冷却剂流动空间;管侧余热排出回路冷却剂区C由余热排出系统换热器入口套筒13内侧、余热排出系统换热器出口套筒15内侧和与其连接的管束8内侧构成的余热排出回路冷却剂流动空间;There are three fluid areas in the heat exchanger: the shell side primary circuit coolant area A, the tube side main heat transfer secondary circuit coolant area B and the tube side waste heat discharge circuit coolant area C; the shell side primary circuit coolant area A is composed of The primary circuit coolant flow space is formed by the inner side of the
壳侧一回路冷却剂区A位于管束8所在区域上部和下部的换热器外壳9同一侧分别开设有一回路冷却剂并联入口窗1和一回路冷却剂并联出口窗2,壳侧一回路冷却剂区A位于壳侧一回路冷却剂并联入口窗1下部横向设置有壳侧一回路冷却剂流量分配孔板7;管侧主热传输二回路冷却剂区B位于下封头12和上封头14的对侧分别开设有二回路冷却剂入口3和二回路冷却剂出口4;余热排出系统换热器入口套筒13的底部和余热排出系统换热器出口套筒15的顶部分别设置余热排出回路冷却剂入口5和余热排出回路冷却剂出口6;The shell-side primary circuit coolant area A is located on the same side of the
一回路冷却剂进入一回路冷却剂并联入口窗1后,经过壳侧一回路冷却剂流量分配孔板7后放热,最后在一回路冷却剂并联出口窗2汇集并流出;二回路冷却剂进入二回路冷却剂入口3后,经过下管板11分配流量,后在管侧吸热,最后在二回路冷却剂出口4汇集并流出;余热排出回路冷却剂进入余热排出回路冷却剂入口5经过余热排出换热器入口套筒13进入管束8吸热,最后在余热排出系统换热器出口套筒15汇集并由余热排出回路冷却剂出口6流出。After the primary circuit coolant enters the primary circuit coolant parallel inlet window 1, it passes through the primary circuit coolant
和现有技术相比较,本发明具备如下优点:Compared with the prior art, the present invention has the following advantages:
二回路和余热排出回路同时在紧凑空间内与一回路冷却剂换热,提高了换热效能。The secondary circuit and the waste heat discharge circuit exchange heat with the primary circuit coolant in a compact space at the same time, which improves the heat exchange efficiency.
壳侧一回路冷却剂、二回路冷却剂与管侧冷却剂逆流换热,有利于降低压降和局部热应力。The coolant of the primary circuit on the shell side, the coolant of the secondary circuit and the coolant on the tube side exchange heat in countercurrent, which is beneficial to reduce the pressure drop and local thermal stress.
二回路冷却剂和余热排出回路冷却剂同向流动,有利于抑制流致振动。The secondary circuit coolant and the waste heat discharge circuit coolant flow in the same direction, which is beneficial to suppress flow-induced vibration.
主热传输与余热传输一体化设计有利于核反应堆小型化。The integrated design of main heat transfer and waste heat transfer is conducive to the miniaturization of nuclear reactors.
附图说明Description of drawings
图1是本发明一种小型核反应堆主热-余热一体式换热器示意图。Fig. 1 is a schematic diagram of a main heat-waste heat integrated heat exchanger of a small nuclear reactor according to the present invention.
图2为图1沿D-D向的剖视图。Fig. 2 is a cross-sectional view along the D-D direction of Fig. 1 .
具体实施方式detailed description
下面结合附图,以小型氟盐冷却高温堆为例,对本发明作详细的说明:Below in conjunction with accompanying drawing, take the small fluorine salt cooling high temperature reactor as example, the present invention is described in detail:
如图1和图2所示,本发明小型核反应堆主热-余热一体式换热器,包括一回路冷却剂并联入口窗1、一回路冷却剂并联出口窗2、二回路冷却剂入口3、二回路冷却剂出口4、余热排出回路冷却剂入口5、余热排出回路冷却剂出口6、壳侧一回路冷却剂流量分配孔板7、管束8、换热器外壳9、上管板10、下管板11、下封头12、余热排出系统换热器入口套筒13、上封头14和余热排出系统换热器出口套筒15。As shown in Fig. 1 and Fig. 2, the main heat-waste heat integrated heat exchanger of the small nuclear reactor of the present invention includes a primary circuit coolant parallel inlet window 1, a primary circuit coolant
所述小型核反应堆主热-余热一体式换热器,其管束8采用三角形排布,一部分管由上管板10和下管板11固定,另一部分管由上管板10和余排换热器入口套筒13固定。In the small nuclear reactor main heat-waste heat integrated heat exchanger, the
换热器内有三个流体区:壳侧一回路冷却剂区A、管侧主热传输二回路冷却剂区B和管侧余热排出回路冷却剂区C;壳侧一回路冷却剂区A是由位于换热器外壳9内侧与余热排出系统换热器入口套筒13外侧、管束8外侧区域构成的一回路冷却剂流动空间;管侧主热传输二回路冷却剂区B是由位于换热器外壳9与余热排出系统换热器入口套筒13之间的管束8内侧、位于下封头12的环形二回路冷却剂入口腔室和位于上封头14的环形二回路冷却剂出口腔室构成的二回路冷却剂流动空间;管侧余热排出回路冷却剂区C由余热排出系统换热器入口套筒13内侧、余热排出系统换热器出口套筒15内侧和与其连接的管束8内侧构成的余热排出回路冷却剂流动空间。There are three fluid areas in the heat exchanger: the shell side primary circuit coolant area A, the tube side main heat transfer secondary circuit coolant area B and the tube side waste heat discharge circuit coolant area C; the shell side primary circuit coolant area A is composed of The primary circuit coolant flow space is formed by the inner side of the
壳侧一回路冷却剂区A位于管束8所在区域上部和下部的换热器外壳9同一侧分别开设有一回路冷却剂并联入口窗1和一回路冷却剂并联出口窗2,壳侧一回路冷却剂区A位于壳侧一回路冷却剂并联入口窗1下部横向设置有壳侧一回路冷却剂流量分配孔板7;管侧主热传输二回路冷却剂区B位于下封头12和上封头14的对侧分别开设有二回路冷却剂入口3和二回路冷却剂出口4;余热排出系统换热器入口套筒13的底部和余热排出系统换热器出口套筒15的顶部分别设置余热排出回路冷却剂入口5和余热排出回路冷却剂出口6。The shell-side primary circuit coolant area A is located on the same side of the
如图1所示,一回路冷却剂进入一回路冷却剂并联入口窗1后,经过壳侧一回路冷却剂流量分配孔板7后放热,最后在一回路冷却剂并联出口窗2汇集并流出;二回路冷却剂进入二回路冷却剂入口3后,经过下管板11分配流量,后在管侧吸热,最后在二回路冷却剂出口4汇集并流出;余热排出回路冷却剂进入余热排出回路冷却剂入口5经过余热排出换热器入口套筒13进入管束8吸热,最后在余热排出系统换热器出口套筒15汇集并由余热排出回路冷却剂出口6流出。As shown in Figure 1, after the primary circuit coolant enters the primary circuit coolant parallel inlet window 1, it passes through the primary circuit coolant
管束8的数量和尺寸取决于具体工况,此处管束8数目和尺寸未定。The number and size of the
以上内容是结合具体的优选实施方式对本发明所作的进一步详细说明,不能认定本发明的具体实施方式仅限于此,对于本发明所属技术领域的普通技术人员来说,在不脱离本发明构思的前提下,还可以做出若干简单的推演或替换,都应当视为属于本发明由所提交的权利要求书确定专利保护范围。The above content is a further detailed description of the present invention in conjunction with specific preferred embodiments. It cannot be determined that the specific embodiments of the present invention are limited thereto. Under the circumstances, some simple deduction or replacement can also be made, all of which should be regarded as belonging to the scope of patent protection determined by the submitted claims of the present invention.
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| CN202111007621.9A CN113689964B (en) | 2021-08-30 | 2021-08-30 | Main heat-waste heat integrated heat exchanger of small nuclear reactor |
| US17/871,792 US12154695B2 (en) | 2021-08-30 | 2022-07-22 | Nuclear reactor main heat and waste heat integrated thermal exchanger |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4098329A (en) * | 1976-07-29 | 1978-07-04 | The United States Of America As Represented By The United States Department Of Energy | Modular heat exchanger |
| US4235284A (en) * | 1976-12-16 | 1980-11-25 | The United States Of America As Represented By The United States Department Of Energy | Heat exchanger with auxiliary cooling system |
| US6909765B2 (en) * | 2003-02-03 | 2005-06-21 | Westinghouse Electric Company Llc | Method of uprating an existing nuclear power plant |
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- 2021-08-30 CN CN202111007621.9A patent/CN113689964B/en active Active
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|---|---|---|---|---|
| JP2008292355A (en) * | 2007-05-25 | 2008-12-04 | Toshiba Corp | Intermediate heat exchanger for fast reactor |
| JP2010066191A (en) * | 2008-09-12 | 2010-03-25 | Hitachi-Ge Nuclear Energy Ltd | Intermediate heat exchanger and fast breeder reactor plant |
| CN103295657A (en) * | 2012-02-29 | 2013-09-11 | 上海核工程研究设计院 | Residual heat removal system of nuclear reactor |
| KR20140075205A (en) * | 2012-12-11 | 2014-06-19 | 한국원자력연구원 | Passive decay heat removal system for liquid metal cooled reactors with enhanced natural circulation cooling capability using a helical type sodium-to-sodium heat exchanger |
| CN103839600A (en) * | 2014-03-18 | 2014-06-04 | 中国科学院合肥物质科学研究院 | Flow measurement device and flow measurement method for pond type natural circulation reactor |
| CN106816186A (en) * | 2017-01-24 | 2017-06-09 | 哈尔滨工程大学 | A kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe |
| CN211906974U (en) * | 2020-01-09 | 2020-11-10 | 中核能源科技有限公司 | An integrated nuclear reactor primary heat exchanger |
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| US20220375634A1 (en) | 2022-11-24 |
| US12154695B2 (en) | 2024-11-26 |
| CN113689964A (en) | 2021-11-23 |
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